ML20024C525

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Drawing Submittal Form Re Preliminary Draft Procedures Concerning Dp 5 1202 06 Concerning Loss of Reactor Coolant & Coolant Pressure
ML20024C525
Person / Time
Site: Crane  
Issue date: 06/11/1970
From: Thomasson F
BABCOCK & WILCOX CO.
To:
BABCOCK & WILCOX CO.
References
TASK-*, TASK-GB B&W-0418, B&W-418, NUDOCS 8307120748
Download: ML20024C525 (13)


Text

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Deit's p //-g sat setow ee attacmatuts stawine esscasetsew Casase swa. ses Y

ews rette v IPCD EP_f 1202 6.. _

Issa of 3liactor r* 1==*/Banctar Coela=t-Pressure Is refsrsni$e to ecuments pertaining to this document in J. J. colit=,'s, May 1 trans=1ttal letter, it appea.rr to us that the majority of objectionability arrises

,1970.

f.rm the details of the ZSAS.

As the ESAS is not in 3&S's scope of supply, this pr=He' ary drsft pescedure has been rswrit.en in. seural areas such that the cPers details of the ZSAS are. to be fillsd-in by Mat. Ed.

Although this is a. re-issue of a pre"-' ary d~-=-as, we are iteW the action taken on your c:x==anta and severs 1 other eka gms that have been made.

r Tour einement.: are resolved es folleen:

Sect.1.,1 - Revised to recent. your comments.

Sect. 2,1st paragrap3r = Revised to reflect your ecuments.

3ect. 2.1.2 - Revised to reflect your ecumes?.s.

Bef. 3 3 and 3.k - Added to recect your cannents.

Seet, k.1 - 2erised to recent your ca=nents.

Sect. b.h.- No revision required due to revisica nsde in Sect. 2.1.0.

Sect. k.6 - Eevised fer e*,.arifiention.

Sect. 51 - Revised to rennet your ecuments.

Sect. 6.1.1.1 - Correct as shavn.

Sect 6.1.2.2 - Deleted in ac=ardance with your em=ne=t; succeeding subsectims ren -se,ed.

8307120748 700611 The seenous& Wunsa c.-2 / Emmesiones las7

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}g-CD se s. inta-g, EP 3 12C2 6 lacs of Eocar.ar Coola=t/2ca t

Sect.'

Sect. 6.2.2.2 - Revised to. reflast your eaunants2 - Isadin n

Sect. 6.2 3 3 - Revised to ref3ect your earments Sect. 6 3.2.2 - Revised to recent your sen==nts Sect. 6.3.2.6 - Revised to allow Met Ed to providSe ents.

Sect. 6.3.3.2 - Revised to aller Met Ed to provide de detail concerning systen ecupments.

etail at secondary Sect. 6.k.13 - Deleted to racect your ecennats Sueceeding subsecticas renumbered.

Sect. 6.4.L6 - Revised to reamet you: causant s.

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Other revisions incande:

Sect. 6.L2.k

"' ;- ' awd as Sect. 6.L2 3 and r

  • 1 far DP 1102 10.

eviset to recast mer title k

Sect. 6.3.k.3'- Eer Sect. 6.3.k.3 added; old Sect

.. 4 Sect. 6.3.k.E - h.--Ared 6 3.k.' 5 and valus far I. 6.3.4.3 renu

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Sect. 6 3.k.5 - Rester.bered 6.3.k.6 and revised ear 2 """*****

Sect. 6.k.L2 - Resumhered 6.k.L3' and revised fre cl elairfiestian.

Sect. 6 k.1.k %d 6.k.L2.

aritiestian.

- "~Keet.' 6.k.L 5 - Wered 6.k.Lh. and revised f Sect. 6.k.L6 - Res=ubered 6.k.1.3.

ar clarifiestian.

Sect. 6.k.2 3' = 3evised to refleet new title ftre ILS 12021 0.

F hh2 F. R. Samassas, Assistant EZS:1st Project Manager es:

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1. G. Verd V. S'. De11este R. P. 3 reeding (w/o emel.)

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PURPOSI

' 1.1 To provide energency precedans to be followed la the event of loss of i

remeter coolant /2ase of'reactar eccleat syntam pnssure, far leak rates greater than 30 spa up to and including 36' rupture.

2.

IlISCE*?f!C:l' 21s procedure describes the astica to be taken in the event of a sud a

ane-u-d decrease in RC system pressure anii pressuriser level, cansed by j

ar rupture in the high pressure envelope of the primary system.

i Rose initial symptans osa2d be esased by a malM.an of the makeup syntam er by steam line ruptars,. as voll as.br a less or omolant fl ram the reactar coalszt systaa In addities,. e dropped aantrol red seals conse e short but appreciable

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drop in IC'syntes pressure-(as nactr as 30 psis in 8 seconds), but the pres re vill recover rapid 2r and increase abate normal aparating pressure as an autanat c

to 60s pcwor occurs.Wcas to be taken in the event of a steam syst em rupture are cowred by EP 12C2 2k, " Stem Supply Sysses L,.,", and estian to be taken far a Makeup System malfunctiat involving loss of makeup is-esvered by DP "I, ass of Beactar Coolant Makeup *..

1202 15 Aetimes-to be taken i.a the event of a dropped eastral rod are esvered in. EP 120210, "CID Malfunction Action".

Iceever the i

operasar should assume the esase of the symyscas described above is a syntam-rupture or leak,.1:aless. another sanse saa be immediately established.

f, 7;

sa to be fallowed in the ewat of RC systaa leak rates less than 30 spa are given in EP 1103 23, "3eactor Coolant Systaa Isaksee and Water menistry Castral"' ad are prescribed in "'l"echnical Specifications far 2ree Mile Isised tInit 1*.

Sia procedure applies to RC systen leak rates greater than 30 spa.

2.1 Sis procedare is dividad inta four categories:

2.1.1 Isak or Lyi.

r Within Capability of One Makcup ?==p to Maistata RC Sysses Pressure and Pressuriser Intel ?.rengt Normal Makeup.'sch.

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T21333

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2.1.2 leak or kyten Wi!.hin capability of Two Makeup Paps to Maintain

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Y *4C Pressure and Pr.ecsuri,er temi in the EP Injection Mode.

g.

2.1.p, Larce Empture (In Ezre::. af Cat @ility of Two Mnkeup Pumps)..

g 2.2.

decovery tran Eigh Pesasure IaJectim caused by Scaething Ot.her b'

t.i Se a 3C System Leak or 2 pture.

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3... E H 2!ZC 2._

i.

3.1.

hehnical specifienties for 2ree.h Isind tamit 1.

3.2 Plaal Safety Analysis 3epart, 2ree MLle Island tanit 1, mapt,ar 6, and f

Chapter ik.

t.

33 DP 1101 01, Plant li=its ad Precautims.

3.k DP 110210. Plat 5hntdan and coaldown.

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b.

LDTr3 AD P!E::'Atm'c::5 k.1 Do not attempt to place the M Syetas in operatim when RC System pressure

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is > 200psig and expose the DE System to pressure la excess of design.

9 (A 200 psig interlock prevents opentag DE-71 at 3C pressures > 200 pais).

4.2 as not anoe nos fram indivianal Ds pesups to exced the high =se alarm setpoint or 3900 spa during er modeor q,.4m to present the.possittlitr

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of 3nz p envitation

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k.3 Limit 25 sprar pump Car to 1700 spa per ytamp by throttling valws35-71A and/or 35-713 as required to limit the possibility of pump cavitation.

h.h Limit EP Injectic= nom to 260 spa per injection path (k) to present sne' possibility of p=np cavitation.

k.5 Do-not operst'e reactor coolant pumps vf.thant sut:ricient EP5I (See DP 5 lici 01, " Plant Operusing limits ad Preemstians" sectim 1.k,.

risar 1.0 - 5.)

k.6

  • Jhen E5 isaw*an is. actuated se psig (increasing) Ril pressure, ecoT vater Saw will be skut-off to the contro1 rod di.%e acters,.'c pu=p secars, ad RC pump seal area. ecolors, and seal.;,=g Jackets and RC pia:p seal injection

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and return linen vill be isolaned. IFader these eendittens reacter mst be tripped and the RC pumps must be steveed i eif atelv to avoid damage to the EC pump seals and notars and to the omsrol rod, drive notors.

1 5

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51 Engineered Safeguards Actuation System setpei=ts are as failews:

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r <y i.

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!*2 3**8) Curuted

...r setsoint MJ par e,ter m (77 I ga,a,esi a mig Dee n ocing RC pressure

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.t aig Increas.'.ng a pressure

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2 m (IP Indestie) neig.

Deareezing ac pressure f.i esis Inernasing 35 Pressure 33 """""! Miss-nois Inanssing B. % sure f 'I 25 Isolation isis Iacreasias RB Pressure i

g' 35 Spray neig (p ays)

Increasing EB 'ressure neig (valves) Increasing 35 Pressure g.

n.w..-

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6.1 Isak er LA-, Withis Arabilf*v e* On Makeue Pas to Maintals *C SWten Pmssure a=d Pressetzer Icel 3reaah Yormal Makeue Path

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6.1.1 Sysytans 6.1.L1

7. w riser level sad Rc systaa pressure decrease t

initiC2r and than hal& sta@ty or besia increasing as lr *;

i pressurizer level control valve opens fully and 1stdara

. ad seal retara coes. are isolated- (Step 6.L2.1)$

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- - 6.1.1.2 Makeup tank level decreases at a ruse apprazinstair eqtud, to the syntan leak rat.e ( ry.mely 1 k. inches i

per utante which is equivalent to e leak rate of approz-instely 30 to-130 spa after letdara and. seal retura Sars are isolated in Step 6.L2.1).

6.1.1 3 Possible high radiation level alarg in reactor Wd**!.

i 6.1.1.k Possible reacter bed 1 A4mg gggg g 1gy31313y3, 6.1.2 Insnediate Actims.

6.1.2.1 Close the letdown isolatica valve (HD-73) and seal return isolstion valve (MD-725).

6.1.2.2 3ednee load as rapidly as possible ir. ;reparattan fer

a. narnal shutdoen.

6.1.2.3 Commance normal shutdown and ecoldarn. Refer to 3P 110210,

" Plant Shutdown and f~=!dM".

6.1.2. k Maintain makeup taak level above the 1st level alar.

I and arlatain pressuri=er level in the operating russe.

(3e operator should here roadv far service a means of adding barated veter (bor a concentration equal to er T21335 L

k siir'stly greater thma ?.C systans concentration) to the makeup tank fram the C1 or the itD systen.]

m: If there is not an adequate supply of borated j

vater available from the CA or WD system, or if the operator is unable to maintain the makeup tank above the low lawl alari from this soureeg or if Pressurizer level drops below the low level alars point, trip the roaator and annually initiate IP injection and close the stop valve

(!W-712) on the discharge line from the askeuft tanks carry out the procedure in Section.6.2 i

beginnias with Step 6.2.2 5 6.1.3 Tollow-up Actica 6.1.3.1 When the plant has been shutdown, and the reactor coolant systa= has been cooled down and depressurized, =enitor reactor bu1J ding radiation levels to determine when it is

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safe to send perso=nel into the 1Mmat to locate and anke preparations for repair of *.he rupture.

6.2 Leak or Nrture Within esenhility of "Ve "skeue N:=es to u intain 'O Ovatem s

Pressure sad Presnur! er *_evel in ** In3eetien Mode 6.2.1 Symptoms y

6.2.1.1 Pressuriser level ami 3tc system pressure decrease rapidly and continue decreasias as pressurizar level control valve goes to full open ad letdown and seal return flows are isolated' (Step 6.2.2.1).

6.2.1.2 Possible reactor b* mar tadiation alsras.

6.2.1.3 letdown starste tank lawl decreasing rapidly (greater than 3 to k inches per minute which is equivalent to a leak greater than 96-130 spa when letdown and seal return flows are isolated in Step 6.2.2.1).

l 6.2.2 Instadiate. Action 6.2. 2.1' Close the letdown isolation valw (!SV3),. the seal retura. isolas* on valve (!C-V25).

T21336

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i 6.2.2.2 If reactor has not alrea# been tripped by the reactor

.1 Protectin systas, trip reactor manually.

I 6.2.2. 3 If HP Injection has not already been actuated automatically, i

initiate manually. C1cee the stop valw (W-712). m the discharge line from the makeup tank.

6.2.2.I6 If RC system pressure and pressuriser le4), continue i

desreasins after inistatim et D inJeetion, carry out procedure far "w 1.y

", Section 6.3.

6.2.2 5 If PC systes pressure and pressurizer lew1 stop decreasing ij or begin to increase upon initiation of IF injection, l

naintain RC systaa pressure and pressurizar lowl as close as possible to the normal operating rage by =anual eentrol of D injection flow and by variation of the

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number of running.YJ pumps.

6.2.3 Follow-up Acti m

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6.2.31 Redu=e nu=ber of runnias reactor coolant pumps to cae

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in each loop.

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6.2.3.2 Cool down, and; depressurize RC System by steaming en l~

the turhiss bypasses. Follow the narana cooldown procedure, P 110211, "Cooldown*, as clasear as possible with the

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ezeeption that engineered safeguards systans, ezeept 4

for the core flooding system, must set be bypassed or isolated. ':he safeguards system will thus be available ta actuate automatically as RC systes pressure decreases ad' reac.or b"N=! pressure increases. Catinue to

.t control. RC system pressure and pressurizar level during the cooldown by varyingIF injection fiev and the number of running W pumps as necessary.

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6.2.3.3 Manually estuate D injection at esig if D j

Injection has. not alrea# been initiated utenatically.

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If the 314'"J reaches the low-law lawl alarm point (this-would take at least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />) before RC system pressure drops to the discharre head of the M pumps where D injection flow is initiated, valves SK-76A and 763 and 2-YTA and 7T3 must be i

T21337

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i, Opened. S e 2 pumps will thus take suction f'

on the R5 energency snap and discharge to the W Pumps through the M coolers. When LP flow injectica 1

is initiated as RC pressure drops below the DI Pump discharge pressure, the 2 pumps will inject directly into the reactw. Se W pumps must then be stopped and valves M Y7A k 773 elosed.

6.23.4 As the RC System pressure decreasee below not positive suctica head required far RC pump operations, or if R5 pres-sure reaches k psig where R5 isolation is initiated', stop the EC pumps immediately. (See eurw of variable 3FSR requirassats UP 11011, " Plant Operating limits. and.

Precantions", Section 1.k. Fig.1.0 5.)

6.2.3 5

  • Then 17 injection and the E System is functioning properly,

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stop the W pumps.

6.2.3.6

'Jhen the 3W57 level decreaser to the low =1ow level alarm point, open the 35 emerm sep su=ti..a valver

("5-V6A and V63), than clase the IWST suetten valves (DE-Y3A and V53).

6.2 3.7 Carry out plant emergency proceduree (pow.daresi by s

Mrtropolitan ? disco Capany).

6.3 1arre_*=rtwe (cr, ster thsn casht3 ttv of Sne w keve %s to u t :t ain a

s RC f**s es 5 essure and

  • esswiter tevel in '!? Tr.4ection v g,)

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6. 3.1 S,

.c=s 6.3.1.1 Rapid and mazplained: decrease in reactor coolant system pressure and pressurizar level, with associated alarms.

6'3.1.2 3eactor 3=4' Mar radiatica scatter alarm 6.3.1.3 Reaetor T 4

  • ae sury hi d lerel alars.

6 3.1.k Scan or all of the following additicaal indicaticar on the catrol recut console and panels: 1) reactor trip and assoeisted alarm. and indicaticas; 2) turbine trip and associated alaras and indications; 3) engineered safeguards actuation indicaticae; k) increasing reactor bu4 ar pressure.

6.3.2 nnedisse Action 6.3.2.1 Verify that reactor trip occurs at er befare 1.*C0 psig.

T21338


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Trip reactor manually at 1800 psig if reactor protectin I

r system fails to faction.

6 3.2.2 Verify that emergency EP injection is initiated at 1500 pois (decreasias) RC system pressun or k psis (increasias)

R5 pressun as follows:

1. '

3e isolation valves in the purification letdown line (DY2A, 21W123, EV3), in the seal retura line (WV26), and in the seal injection line (MU-720),elose.

2.

Two non-operating M!! pumps start, operating makeup pump stops.

3.

Energency iaJeetion valves %V16A,. 3, C and D opea.

k.

3 crated water storage tank isolstion valws DV1kA and' S Y1kB open.

If any of these functims fail to actuate autmatically, the operator should actuase them annually.

6.3.2.3 Verify that LP indestim is initiated at usig (decreasias) RC sysses pressure or k psig- (increasing) 5 pressure,. as fellows:

3 IF !aJeetim valves- (NYkA and Yk8) sad 325T value

( N Y5A'and V53)'open.

2.

Se two 2 pu=rs start and operate in the bypass ande until the RC system pressure decreases below the DE pu=p discharge pressure.

3.

Decay heat river water and doesy hess closed eyele pups start.

k.

Decay heat river water pump discharp.= valves open.

5

.".uelear services coolias water systes(s) eussa (Mat Ed provide).

If my of these functions fail to actuate atomaties117.

the operatar should actuate them annually.

6.3.2.5 If 35 pressure isenases ta voir, writy that 23 isola-tion is initiated, and that the R3 sooling system is neig increasine 2 pressure only.

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i shifted to the enerency mode as fouews:

1.

Se three recirculation air handling unit.s are ennrgized and operate at low speed.

.2.

Se R5 emergency coolina pumos stan.

3.

Se energency cooline coil isolation vulve en the outlet side of each esil opens, and the nor=si ecoling coil isolation valves elese.

6 3.2.6 Verify that the R3 sprar system is actuated automaties21:r at (Met 34 provide) as fo11ews:

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i I

(Met Ed Provide)

If aar of these functions fail to actuate autcu:sticall:r.

the operster should acutate them==Ev.

l 6.3 3' Follow-up Action i

6.3 3 1 Stop reactor cool ms pu=ps.

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6.3 3 2 Thra off anda and emergener feedwater y==ps; close =ais and emerncy feedwater stop valves.

6.3 3 3 Insure turbine has tripped: it not,tri; =an c.

6 3 3.V hrottle IP injection valves D*.J 16A, 3, C-and ;)

i as.necessary to prevent pump runaut.

i 6 3 3.-3 Close the stop valve (%l*-712) on the discharre line from r

the ankeup tank.

6 3 3.6 After initiatim of I.? injection, when the IE yu.. s are running and the IEt system is nsesioni=g properly a

stop the 15 pumps.

6337

'Jhen the 31r.TT level decreases to icv-le' level sisr=

point, open the R5 e=ergency sum = suctica valves (2-76A and V63), then close the 3::3" sucti=n valvec ('3* ~3A end V53), the sodium thianulfate tank eutlet valves (?

  • at, and Yk3) and the sodium :.se 4de tar.h outlat vsivvs (33-PA and 723).

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6.3 3.8 Carry out p1= t a=errency procedures (precedures by Metglitan Edisca Campany).

6.3.k Long fera Action (NOTE:

"he purpose of this sectica is to describe additional estia related to the ene:ineered safeeuards systen vitich are to be taken by the operster in the post accident period. Maring this period the reacter bulla1.v: pressure est be-nduced to atmospheric, the reacter buildiac integrity must be maintained and core deeny hest an=2 j

be removed until such ti=e as me reactor buildiac can I

be safely entered and plant repsi s and recoverr initistad).

6.3.k.1

)

Secure the turbine, the

  • feed system, and the stem systen.

63.I.2 Sample the boros con =entragica of the reactor buildine sump to insure that the bores cementrstien is not reduced by dilution with unborsted vster.

If the boroa escentration of 2e reactor Wdd M su=p vaser being recirculated 3.hrouah the 17 systu shesid I

dearesse below (later) pyn, toric acid =ar be added b7

._one of the following methods:

From horic acid pu=ns via the Spe= ?:e1 Coolier s.

System to the suctim of the 3 pu==s. (Ces=entnt.1:n.

of borie acid being pu= ped must be below the-veint percent which vill precipitate as the ambie=. tec=.

of the SF cooling systes piping, e.g., d.M st TCF.)

b.

37 refilling (or partially filling) the 3C vish 5 veight % beric acid solutica fec= the CA s rsten I

and *.han shifting the suctica of ace of the 2

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pumps. temporarily to the 3W57 until the low-low a

lawl alarm is. reached.

6. 3. 16 3 Sample the 35 sump water for ?2 and for thiosuefite concentratica. If the ?H droes below, sodium hydroxide must be added to the suun water to bring the 7E bach within allovsace. If the thisd-'*ite ecces=tntic: t =ps below, sodium thiosulfite shculd be added to the 5 s :.

veter to bring the concentration bach vithis alleve.::e.

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f

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10

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s D ese chemicals enn be added (separately) f.on the CA system through the !!J system. De potaanium hydroxide

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addition tank on the horie acid mix tak may be used to mix and laJect hte sodium hydroxide and thiosulfate i

solutton.

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6. 3. k. k Wen the post accident reactor buildi=c pressure is nduced to about 10 psig, return the reactor building cooling fas to thil speed to reduce the buildine. tagerature end pressure at a faster rate.
6. 3. k. 7 Monitor the lyrd.4 level in the asesor bum'ai.

Carry i

ont the appropriate procedure

  • for hydrocen renoval when hydrogen level reaches 3 5.T by volume.

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6.3.k. 6 2e R5 spray system should be maintained in opention for 4

80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br /> follarintr a large ruptun loss of coolant sepident. Be spray system any be seennd after this tir.e

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c if per=itted.by the iodine lent in the R5.

s 6.k Reeeeere f: = Acutatice** ef U Indeetten caused be ^the-S-= a **

S rste= lesk er M st :r, 6.k.1 Symptomt r

6. k.1.1 Sudden decrease la RC System pnssure and pnssurizer 1mul.

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6.k.1.2 D injection actuated with associated alar =s and is!.1:stions.

6.k.1 3 Reactor trijt with associated sla==s and: indiestiens.

(If Rtr pressure has dropped sufficiently to case nactor protective systen to. fanation).

1

6. k.1. k LP iaJection actuated with associated ala; m and indi=sticas.

I (If Ic pressure has 4.e,,d to esig) 6.h.1 5 ac system pnssure and presse.:er leni stop deenasing and begin increasing rapidly after 167 pumps start.

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l 6.k.2 Immedisse Actica

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6.k".2.1 Stop P iaJectics when pressuriser level is nstand to I,

. normal opers ing range (above' low level alarm pot =t).

  • Metrepolitan Edis-n Company provide
    • %s actuation may have been initiated autmaatically, or =ssuall" he etermtar u a result e.

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11 Case 1C suction vnives (7%VlhA and 71kD) from FC and HP injection valves (!C-V7AA, 3, C nnd D).

S tt,p runnia6 W Peps and restart nomativ operating :*.J pur:p.

6.h.2.2 Restare W syntes (incind'ng seal im4ection, sesi ntura ad letdown) to nomal operattar lineun.

4.h.2 3 Determine esuse of deensse in pressure and pressu.-iar level and carry out appropriate e=errence precedum, e.r.,

" Steam System

(IIP 1202 Ok), "CR314altuartion Acties" (?? 1202 10), etc.

6.k.3 Tollow-up Action 6.k.3.1 Investigate and repair cause Of 9mase is 30 syst==

pressure and pressurizar level.

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